Event Notification Report for November 22, 2000
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
11/21/2000 - 11/22/2000
** EVENT NUMBERS **
37539 37540 37541 37542 37543 37544
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|Power Reactor |Event Number: 37539 |
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+------------------------------------------------------------------------------+
| FACILITY: FITZPATRICK REGION: 1 |NOTIFICATION DATE: 11/21/2000|
| UNIT: [1] [] [] STATE: NY |NOTIFICATION TIME: 01:12[EST]|
| RXTYPE: [1] GE-4 |EVENT DATE: 11/20/2000|
+------------------------------------------------+EVENT TIME: 23:10[EST]|
| NRC NOTIFIED BY: MIKE RASTLEY |LAST UPDATE DATE: 11/21/2000|
| HQ OPS OFFICER: DOUG WEAVER +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |CURTIS COWGILL R1 |
|10 CFR SECTION: | |
|AINB 50.72(b)(2)(iii)(B) POT RHR INOP | |
|AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | |
|NLCO TECH SPEC LCO A/S | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 75 Power Operation |72 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
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| HPCI INOPERABLE - TURBINE EXHAUST LINE FLOODED |
| |
| HPCI turbine exhaust drain pot level switch has malfunctioned. This has |
| potentially led to a condition where exhaust line from the turbine is |
| flooded. GE SIL 580 recognizes that a slug of water can create a momentary |
| high pressure and rupture both exhaust line rupture diaphragms if HPCI |
| should initiate. |
| |
| HPCI system has been declared inoperable and the licensee entered a 7 day |
| LCO. |
| |
| The NRC resident inspector has been notified. |
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|Power Reactor |Event Number: 37540 |
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| FACILITY: FITZPATRICK REGION: 1 |NOTIFICATION DATE: 11/21/2000|
| UNIT: [1] [] [] STATE: NY |NOTIFICATION TIME: 11:03[EST]|
| RXTYPE: [1] GE-4 |EVENT DATE: 11/21/2000|
+------------------------------------------------+EVENT TIME: 10:22[EST]|
| NRC NOTIFIED BY: AMBRAMSKY |LAST UPDATE DATE: 11/21/2000|
| HQ OPS OFFICER: DOUG WEAVER +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |CURTIS COWGILL R1 |
|10 CFR SECTION: | |
|AARC 50.72(b)(1)(v) OTHER ASMT/COMM INOP | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 93 Power Operation |93 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| LOSS OF POWER TO THE EMERGENCY OPERATIONS FACILITY (EOF) |
| |
| The loss of power to the EOF impairs the ability of the licensee to carry |
| out the plant's emergency plan. A snow storm is being blamed for the loss |
| of power. |
| |
| The licensee notified the NRC resident inspector. |
| |
| (Refer to event number 37541 for a related event at Nine Mile Point.) |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37541 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: NINE MILE POINT REGION: 1 |NOTIFICATION DATE: 11/21/2000|
| UNIT: [1] [2] [] STATE: NY |NOTIFICATION TIME: 11:29[EST]|
| RXTYPE: [1] GE-2,[2] GE-5 |EVENT DATE: 11/21/2000|
+------------------------------------------------+EVENT TIME: 09:50[EST]|
| NRC NOTIFIED BY: QUINTON HICKS |LAST UPDATE DATE: 11/21/2000|
| HQ OPS OFFICER: DOUG WEAVER +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |CURTIS COWGILL R1 |
|10 CFR SECTION: | |
|AARC 50.72(b)(1)(v) OTHER ASMT/COMM INOP | |
| | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |100 Power Operation |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| LOSS OF POWER TO THE EMERGENCY OPERATIONS FACILITY (EOF) |
| |
| The licensee reported that power was lost to the EOF at 0950 and was |
| restored at 1045. This facility serves both the NMP units as well as |
| Fitzpatrick. The licensee notified the NRC resident inspector. |
| |
| (Refer to event number 37540 for a related event at Fitzpatrick.) |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Other Nuclear Material |Event Number: 37542 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: BEST INDUSTRIES |NOTIFICATION DATE: 11/21/2000|
|LICENSEE: BEST INDUSTRIES |NOTIFICATION TIME: 12:02[EST]|
| CITY: SPRINGFIELD REGION: 2 |EVENT DATE: 11/21/2000|
| COUNTY: STATE: VA |EVENT TIME: 10:00[EST]|
|LICENSE#: 45-19757-01 AGREEMENT: N |LAST UPDATE DATE: 11/21/2000|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |MIKE ERNSTES R2 |
| |JOHN HICKEY NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: JOE WANG | |
| HQ OPS OFFICER: BOB STRANSKY | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|BAAA 20.1906(d) SURFACE CONT/ EXT RAD | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
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| 10 CFR PART 20.1906(d) REPORT |
| |
| One of three Type A shipping packages received from Baylor University |
| exceeded the limit for surface radiation readings (200 mR/hr). The licensee |
| reported that the package was reading 2.7 R/hr at the surface of the |
| package, and 65 mR/hr at 1 meter. The package has been placed in safe |
| storage. The licensee will contact Baylor University and the shipper |
| (FedEx). |
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+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 37543 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: COLORADO DEPT OF HEALTH |NOTIFICATION DATE: 11/21/2000|
|LICENSEE: PHOENIX SURVEYS, INC. |NOTIFICATION TIME: 15:36[EST]|
| CITY: BRIGHTON REGION: 4 |EVENT DATE: 12/23/1999|
| COUNTY: STATE: CO |EVENT TIME: [MST]|
|LICENSE#: 838-01 AGREEMENT: Y |LAST UPDATE DATE: 11/21/2000|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |GAIL GOOD R4 |
| | |
+------------------------------------------------+ |
| NRC NOTIFIED BY: TIM BONZER (fax) | |
| HQ OPS OFFICER: BOB STRANSKY | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| AGREEMENT STATE REPORT - ABANDONED WELL LOGGING SOURCE |
| |
| "Date of Occurrence: 12-23-99. |
| |
| "Description of Source: Am241Be sealed source Gulf Nuclear model: 712A, |
| serial number: |
| 635B, physical form: Solid, quantity: 20Ci. |
| |
| "Well Operator: Colorado Energy Minerals, Inc. |
| |
| "Well Name: UPRC Baur 17-1 |
| |
| "Surface Location: NW NE 600' FNL 2000' EEL Sec-17, Twp-9N, Rge-64W. |
| |
| "Results of efforts to seal and immobilize the source: The source is at the |
| bottom of the hole with 100' of red cement above. A used drill bit has been |
| cemented in as a deflector in one of the uphole plugs. |
| |
| "Description of attempted recovery: It was discovered the source was in the |
| hole without the protection of the pad carrier. It was verified with a gamma |
| ray to be on the bottom of the hole. Fishing was attempted via the wireline |
| with a magnet since the holder was magnetic. These attempts were hampered by |
| steadily deteriorating hole conditions and fill on top of the source. |
| Fishing attempts involving use of the drilling rig and pipe were ruled out |
| due to the possibility of source rupture from the extreme weight of the |
| drill string. When the fishing attempts proved unsuccessful it was |
| determined to cement the source in the hole. A final gamma ray was ran to |
| assure the source was at the bottom of the hole and the well was plugged as |
| outlined above. Note: The well was a dry hole and the well was plugged with |
| cement plugs at various depths and the deflector cemented in one of these |
| plugs. |
| |
| "Depth of the source: 4420'" |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37544 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: HOPE CREEK REGION: 1 |NOTIFICATION DATE: 11/21/2000|
| UNIT: [1] [] [] STATE: NJ |NOTIFICATION TIME: 16:12[EST]|
| RXTYPE: [1] GE-4 |EVENT DATE: 11/21/2000|
+------------------------------------------------+EVENT TIME: 13:08[EST]|
| NRC NOTIFIED BY: ART BREADY |LAST UPDATE DATE: 11/21/2000|
| HQ OPS OFFICER: BOB STRANSKY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |CURTIS COWGILL R1 |
|10 CFR SECTION: | |
|AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | |
|NLCO TECH SPEC LCO A/S | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |100 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| BOTH TRAINS OF CONTROL ROOM EMERGENCY FILTRATION INOPERABLE SIMULTANEOUSLY |
| |
| "At 1308 hours, the 'B' Control Room Chiller tripped on an apparent high |
| bearing oil temperature condition, rendering the 'B' Control Room Emergency |
| Filtration (CREF) train inoperable. At the time that the 'B' CREF train |
| tripped, the 'A' CREF train was out of service for scheduled maintenance. |
| With both trains of CREF inoperable, Technical Specification 3.0.3 was |
| entered. Preparations were made to commence plant shutdown in parallel with |
| restoration of the 'A' train from maintenance. The 'A' CREF train was |
| returned to operable status at 1402 hours and Technical Specification 3.0.3 |
| was exited. A seven-day action statement remains in effect for the |
| inoperability of the 'B' CREF train. |
| |
| "The Control Room Ventilation System provides heating, cooling, ventilation, |
| and environmental control for the control room and adjacent areas. Under |
| accident conditions, the Control Room Emergency Filtration Unit ensures that |
| the control room will remain habitable during and following all design basis |
| accidents. Because the CREF system is required to automatically respond in |
| the event of a design basis accident, having both trains of CREF inoperable |
| at the same time impacted the ability to mitigate the consequences of an |
| accident. Therefore, this event is being reported in accordance with |
| 10CFR50.72(b)(2)(iii)(D). |
| |
| "All other safety related equipment is operable with the exception of the |
| 'C' Main Steam Line Radiation Monitor, which is in the tripped condition due |
| to a surveillance test failure. A root cause investigation team has been |
| assembled to determine required corrective actions." |
| |
| The NRC resident inspector has been informed of this notification by the |
| licensee. |
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Page Last Reviewed/Updated Thursday, March 25, 2021
Page Last Reviewed/Updated Thursday, March 25, 2021